Neutron Activation - for Dosimetry

RRDF-98

Russian Reactor Dosimetry File.  K.I. Zolotarev, A.V. Ignatyuk, V.N. Manokhin, A.B. Pashchenko. Cross sections and covariance matrices of uncertainties for 22 reactions used for neutron flux dosimetry by foil activation. Summary description:  IAEA-NDS-193 with links to data and figures.
 

IRDF-90

The International Reactor Dosimetry File, version 2 of Oct. 1993. Summary documentation: IAEA-NDS-141, Rev. 3. This includes internationally recommended cross-sections with covariance data for a selected set of activation reactions used for reactor neutron dosimetry by foil activation. About half of the reactions has been taken over from ENDF/B-6; the other half are original evaluations prepared for IRDF-90. Available for downloading or on tape or PC diskettes, or by FTP.

For an introduction see the textbook "Nuclear Data Guide for Reactor Neutron Metrology", by J.H. Baard, W.L. Zijp, H.J. Nolthenius, Kluwer Academia Publishers (1989). - Not available from IAEA.

For a survey of a number of properties of IRDF-90 data (first version of 1990) see the reports:

The above mentioned report NEA/NSC/DOC(93)3  is a comprehensive source of information on  the processing of covariance data in general.

NMF-90

Neutron Metrology File, an integrated database for performing neutron spectrum adjustment calculations. Documented in reports IAEA-NDS-171 and INDC(NDS)-347 by N.P. Kocherov. It contains the IRDF database, together with 4 different adjustment codes, 6 data sets for reactor benchmark neutron fields, and utility codes for processing and plotting the input and output data. The package consists of 9 PC HD diskettes and code manuals. 10 Mb of diskspace is required. The diskettes may be downloaded from here or be sent by ordinary mail.

Neutron Excitation Function Guide for Reactor Dosimetry

by O. Gritzay, M. Vlasov, L. Chervonna, V. Zerkin, N. Klimova, G. Kolota (January 2002). Intercomparison of 81 dosimetry reactions for 56 nuclides. Available on CD-ROM or online.

ENDF/B-6 Dosimetry File

Partly superseded by IRDF-90. Not maintained as a separate data library; see the general ENDF/B-6 Library, documented in IAEA-NDS-100.

JENDL Dosimetry File 99 (JENDL/D-99)

Available on CD-ROM. Data for 67 dosimetry reactions in pointwise and 641 group structure form. Figures in PDF format.
Summary documentation: IAEA-NDS-140.

PRONDOS

Evaluations of selected neutron activation reactions for dosimetry by V.G. Pronjaev et al. 1988/89.
Summary in document IAEA-NDS-142.

Other dosimetry reaction files may be included in the General purpose evaluated neutron nuclear data.

The following should be regarded as superseded by more recent files:

IRDF-85, the International Reactor Dosimetry File.
Summary documentation: IAEA-NDS-41, Rev. 1. This includes 640-group data derived from ENDF/B-5 Dosimetry File Rev. 2, ENDF/B-5 Gas Production File Rev. 2, some evaluations from INDL/V, two radiation damage files for iron, and 10 benchmark neutron spectra. Available also as cross-sections without resonance-parameters. The cross-section data are superseded by IRDF-90. The benchmark neutron spectra remain of interest.

ENDF/B-5 Dosimetry File: Rev. 2 (1984). Also available as 620 group data. Summary documentation: IAEA-NDS-24, Rev. 2.
This file is superseded by the ENDF/B-6 Dosimetry File.

DOSCROS84, dosimetry cross-sections by ECN Netherlands, in 640 group structure. Documentation by W.L. Zijp et al. in ECN-160. This data file is referred to in the book by J.H. Baard, W.L. Zijp, H.P. Nolthenius: "Nuclear Data Guide for Reactor Neutron Metrology"; Kluwer Academic Publishers, 1989. Whereas the book continues to be useful, many of the numerical data included should be replaced by more recent data such as IRDF-90.

BOSPOR-78 and BOSPOR-80, threshold neutron reactions by F.E.I. Obninsk. These data were compiled by the IAEA Nuclear Data Section into ENDF/B-5 format. They are included in INDL/V (see General purpose evaluations).

UKNDL-81 Dosimetry File: This was extracted by NDS from UKNDL-81. UKNDL format plus one additional character to allow for four digit DFN numbers.

DETAN74. Based on files by W.N. McElroy from HEDL (USA), prepared by A. Fabry from CEN/SCK Mol (Belgium), documented by H.C. Rieffe and H.J. Nolthenius from ECN Petten (Netherlands) in Report RCN-75-139, Oct. 1975.